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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
WIPP improves utility shaft safety, begins infrastructure project
Harrison Western Shaft Sinkers (HWSS), the company drilling a new utility shaft at the Department of Energy’s Waste Isolation Pilot Plant in New Mexico, has retained a safety culture expert following a near-miss accident in the shaft late last year. The safety expert will conduct monthly facilitated discussions with crews working on the shaft to reinforce expectations for identifying concerns regarding unsafe circumstances, according to a recent report by the Defense Nuclear Facilities Safety Board (DNFSB).
Tom Elicson, Hugh Luo, David Luxat (Jensen Hughes), Lajos Tarczal (Paks Nuclear Power Plant), Tom Kindred (EPRI)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 365-378
The MAAP v5.03 computer program was modified to incorporate the unique features of the VVER plant design to provide a state-of the-art severe accident analysis code for the VVER plants. The MAAP5-VVER code is applicable to the VVER-440, VVER-1000, and VVER-1200 plant designs and is capable of accurately modeling scenarios with in-vessel melt retention (IVMR), which is a crucial VVER accident management strategy, and PRISE accidents (large primary-to-secondary leaks) which are key contributors to plant risk. The MAAP5-VVER code version is intended to be applied to accident management analyses as well as Level 1 and Level 2 PRA analyses.
To ensure that the MAAP5-VVER code adequately addresses phenomena and capabilities important to the expected VVER applications, the MAAP5-VVER code is undergoing verification and validation (V&V) testing prior to final code release. The V&V test plan is designed to provide complete coverage of the MAAP5-VVER specific models and important modeling capabilities. Additionally, the validation exercises consist of data for both the VVER-440 and VVER-1000 plants designs obtained from scaled experiments, full scale plant tests, and other detailed code calculations.
This paper provides an overview of the MAAP5-VVER modeling capabilities, discusses the MAAP5-VVER V&V testing program, and presents preliminary results for a benchmark against the IAEA-SPE-3 test performed at the PMK-2 scaled test facility.